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Core Design Study for a 500MWe Fast Oxide Reactor

Description: A 500 MWe sodium-cooled, PuO2-UO2 fuel, fast spectrum reactor design is presented, which is calculated to have a fuel cycle cost in the civinity of 1 mill/ekw hr, and to have important safety features due to an appreciably negative Doppler effect.
Date: December 28, 1961
Creator: Horst, K. M.; Hutchins, B. A.; Leitz, F. J. & Wolfe, B.
Partner: UNT Libraries Government Documents Department
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Failure Analysis of Dispersion Fuel Elements Based on Matrix Cracking

Description: A mathematical model has been developed for estimati the burnup at which mechanical failure occurs in dispersion fuel elements. It is postulated that failure at low temperature, < 900 deg F, occurs as a result of brittle fracture of an elastic matrix when the intensity of the stress locally reaches the ultimate strength of the material. The contributions of fission gas pressure and thermal stress are incorporated in the stress analysis. Because of the complexity of the stress distribution and t… more
Date: December 28, 1961
Creator: Beck, S. D.
Partner: UNT Libraries Government Documents Department
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REMOTELY CONTROLLED SHEARING OF PIPE AND STRUCTURAL MEMBERS

Description: A shearing tool was developed for remotely controlled severing of pipes or structural members. The shear is rotated about its axis in a wrist motion by the pumped hydraulic fluid that also powers the shear blade. It can be used in a stationary mounting or suspended from a crane. A C-shaped support for the shear was designed to pass through a small top opening of a shielded cell. The controls for manipulating the shear pass through or along the Cframe. The shear jaw opens to 5 in. in height and … more
Date: December 28, 1961
Creator: Abbatiello, A. A.
Partner: UNT Libraries Government Documents Department
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Experimental Stress Analysis of Egcr Pressure Vessel. Part 1. Experimental Determination of Stresses in Model. Part 2. Interpretation of Experimental Results and Examination for Structural Intergity

Description: Structural evaluations of the upper head of the EGCR pressure vessel were made. The configuration throughout the cluster region in the vessel was found to be structurally adequate. The primary and primary-plus-secondary stress intensities for the burst-slug detection and gas outlet nozzles were found to be within the allowable limits. However, the complete design evaluations of these units cannot be made until the temperature distributions are known. (auth)
Date: November 28, 1961
Creator: Holland, R. W.; Maxwell, R. L.; Witt, F. J.; Shobe, L. R.; Greenstreet, B. L.; LaVerne, M. E. et al.
Partner: UNT Libraries Government Documents Department
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Non-Destructive Analysis of Uranium in Graphite Fuel Elements by Neutron Activation

Description: A method is presented for the determination of uranium (as U/sup 238/) in uraniuni-loaded graphite fuel elenients by a non-destructive, direct radioactivity analysis technique. A 200-cbannel pulse-height analyzer, equipped with a 3 in. x 3 in. NaI(Tl) crystal, is used to measure the Np/sup 239/ radioactivity of the neutron-irradiated samples. The amount of U/sup 238/ in the test samples is deterimined quantitatively by comparing the Np/sup 239/ radioactivity induced in each sample with the Np/s… more
Date: November 28, 1961
Creator: Bate, L. C.; Hampton, W. J. & Leddicotte, G. W.
Partner: UNT Libraries Government Documents Department
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Small Power Reactor Projects of the United States Atomic Energy Commission

Description: Information on small power reactor projects of the USAEC is summarized. General information concerning the projects as a whole is given. Specific projects discussed include: the Elk River Power Reactor, the Piqua Nuclear Power Facility, the BONUS Power Reactor, the Pathfinder Power Reactor, the small-size pressurized water power reactor, and the experimental low-power process heat reactor. (M.C.G.)
Date: September 28, 1961
Partner: UNT Libraries Government Documents Department
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GAS-COOLED REACTOR PROGRAM. QUARTERLY PROGRESS REPORT FOR PERIOD ENDING JUNE 30, 1961

Description: Activities are discussed for research in design investigations, and materials development and testing conducted in connection with the development of the EGCR. The discussions are given in terms of: reactor physics; reactor design studies; heat transfer and fluid now investigations; materials development; in- pile and out-of-pile testing of components and materials; and development of test loops and components. (B.O.G.)
Date: August 28, 1961
Partner: UNT Libraries Government Documents Department
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Post irradiation examination of self support elements with severe in-reactor cladding corrosion (RM425)

Description: Three self support, natural uranium, I & E production fuel elements, which exhibited serious in-reactor cladding corrosion were selected from several tubes of discharged pieces from PT-IP-272-A-FP. The elements were transferred to the Radiometallurgy Laboratory for detailed examination to determine thickness of the remaining cladding and measure any irradiation induced dimensional changes in the fuel cores. Each element had four support tabs attached to each end and was from Parent Lot KT.009. … more
Date: August 28, 1961
Creator: Gruber, W. J.
Partner: UNT Libraries Government Documents Department
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Post irradiation examination of transverse cracked rupture from 2986 DR (Rm 427)

Description: An O III N, I and E dingot element exhibited several transverse cracks when it failed in tube 2986 DR. Detailed examination in the Radiometallurgy Laboratory was requested to determine the cause of failure and obtain the ingot number. The element was so badly damaged that it was impossible to determine the exact cause of failure. Reaction between the coolant and fuel occurred at the internal surface around the spire over the total length of the element. Reaction was the greatest near the midpoi… more
Date: August 28, 1961
Creator: Gruber, W. J.
Partner: UNT Libraries Government Documents Department
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A Program of Research and Calculations of Resonance Absorption. Final Report

Description: A direct numerical integration of the integral equation for the average collision density in the absorber was previously suggested in a discussion of resonance absorption. The implementation of this program is considered. The method of calculation, comparison with experimental data, and the computer code developed are described. The method of integration, computation of cross sections, selection of mesh size, integration interval, outside correction, the Dancoff correction, and unresolved reson… more
Date: August 28, 1961
Creator: Nordheim, L. W.
Partner: UNT Libraries Government Documents Department
open access

Conceptual Design of an In-Pile Package Loop for Fast Reactor Fuel Testing

Description: Report issued by the APDA over a design study conducted on an "in-pile package loop for use as a reactor fuel test facility" (p. 5). The results are presented and discussed. This report includes tables, and illustrations.
Date: July 28, 1961
Creator: Blessing, W. G.; Balsbaugh, R. R.; Bloomfield, D. E.; Busch, J. S.; Hennig, R. J.; Jens, W. H. et al.
Partner: UNT Libraries Government Documents Department
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Test of Buried Structural-Plate Pipes Subjected to Blast Loading

Description: From abstract: Two 20-ft-long 7-ft-diameter 10-gauge structural-plate pipes, having longitudinal joints with eight bolts per foot, were buried and tested in the Smoky event of Operation Plumbbob at predicted pressure levels of 195 and 265 psi. The depth of burial was 10 ft over the crown of the pipe.
Date: July 28, 1961
Creator: Williamson, R. A. & Huff, P. H.
Partner: UNT Libraries Government Documents Department
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Analytical considerations for K-Downcomer and bellows for General Electric Company

Description: This report details model studies performed as required by the design, development, and research contract between the General Electric Company and Washington State University. These studies provide analytical considerations for K-Downcomer and Bellows.
Date: June 28, 1961
Creator: Lomax, C. C.
Partner: UNT Libraries Government Documents Department
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Cost estimate for reduction of P{sub 32} in reactor effluent

Description: The proposal to reduce P{sub 32} in reactor effluent by increasing aluminum sulphate and bauxite feed to 18 ppm while maintaining 7.0 pH water is estimated to cost $1,368,000. This represents an increase of $507,000 over FY 1962 budgeted cost for aluminum sulphate, bauxite and sulphuric acid. The basis for the cost estimate is provided, and detail calculations are given.
Date: April 28, 1961
Creator: Tolman, H. R.
Partner: UNT Libraries Government Documents Department
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EVIDENCE FOR A T = 0 RESONANCE IN THE V * SYSTEM

Description: In previous letters the authors have reported a {Sigma}{pi} resonance observed through the study of the interaction of 1.15-Bev/c K{sup -} meons in hydrogen in the Lawrence Radiation Laboratory 15-in. bubble chamber. They now wish to report the results of the study of the three reactions: (1) K{sup -} + p {yields} {Sigma}{sup +} + {pi}{sup -} + {pi}{sup -} + {pi}{sup +}; (2) K{sup -} + p {yields} {Sigma}{sup -} + {pi}{sup +} + {pi}{sup +} + {pi}{sup -}; and (3) K{sup -} + p {yields} {Sigma}{sup… more
Date: April 28, 1961
Creator: Alston, Margaret H.; Alvarez, Luis W.; Eberhard, Philippe; Good,Myron L.; Graziano, William; Ticho, Harold K. et al.
Partner: UNT Libraries Government Documents Department
open access

Evidence For a T = 0 Resonance in the Z[ ] System

Description: In previous letters we have reported a Av resonance, called Y*1, observed through the study of the interaction of 1.15-Bev/c K* mesons in hydrogen in the Lawrence Radiation Laboratory 15-in. bubble chamber. We now wish to report the results of the study of the three reactions [formula](1), [formula](2) and [formula](3).
Date: April 28, 1961
Creator: Alston, Margaret H.; Alvarez, Luis W., 1911-1988; Eberhard, Phillippe; Good, Myron L.; Graziano, William; Ticho, Harold K., 1921-2020 et al.
Partner: UNT Libraries Government Documents Department
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Flexible Monte Carlo Programs FMC-N and FMC-G

Description: Flexible Monte Carlo programs FMC-N and FMC-G (GE-ANPD Programs 516 and 515) are digital computer programs which apply Monte Carlo methods to simulate neutron and gamma ray life histories, respectively, in a source-shield configuration. The programs were designed for flexlbility in the geometrical, material, nuclear, and source descriptions of source-shield configurations and variance reduction techniques. The programs were also designed to optimize the use of fast memory and to provide complet… more
Date: April 28, 1961
Creator: Loechler, J. J. & MacDonald, J. E.
Partner: UNT Libraries Government Documents Department
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Preliminary MSRE Gamma Ray Source and Biological Shielding Survey

Description: The major gamma ray sources and some of the resultant biological shielding requirements have been evaluated at both full power operation and following shut down for the Molten Salt Reactor Experiment. The sources include gamma rays due to the fission events in the reactor and those associated with activation of materials. Shielding estimates were made for the reactor system cells and for some maintenance facilities.
Date: April 28, 1961
Creator: Vroom, D.W.
Partner: UNT Libraries Government Documents Department
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Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Summary Report, May 1, 1960 to March 31, 1961

Description: Abstract: "Experimental investigation of aerosol particle capture by evaporating and condensing water drops has shown that capture is a function of the rate of water drop growth and aerosol particle diameter. Capture was found to be proportional to the rate of water vapor condensation and inversely proportional to aerosol particle diameter. The influence of water vapor gradient and particle size on aerosol particle capture during evaporation is insignificant. The experimental results are explai… more
Date: April 28, 1961
Creator: Rosinski, John
Partner: UNT Libraries Government Documents Department
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Nuclear Characteristics of Possible Replacement Reactors for the HRT

Description: This data in this report summarize nuclear characteristics on several variables for possible replacement reactors for the Homogenous Test Reactor (HRT) at the Oak Ridge National Laboratory.
Date: March 28, 1961
Creator: Vondy, D.R. & Tobias, M.
Partner: UNT Libraries Government Documents Department
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Research project, Contract CA-264, chemical milling of counterbore recesses in the uranium wall of Zircaloy-2 clad uranium tubes. Final report

Description: This document provides the final report on the research project of chemical milling of counterbore recesses in the uranium wall of Zircaloy-2 clad uranium tubes. The scope of work, results and conclusions, and experimental procedures are provided.
Date: March 28, 1961
Creator: Atkins, D. C. Jr.
Partner: UNT Libraries Government Documents Department
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TrU Facility - Alpha Box Accessories - Spherical Joint Clamp

Description: This report details the specifications of a clamp designed to be remotely manipulator operator and which clamps a standard spherical (glass) joint. This clamp was needed and will be used in conjunction with operational equipment within an alpha-tight box used in connection with the Transuranium process in the TrU Facility.
Date: March 28, 1961
Creator: Klima, B.B.
Partner: UNT Libraries Government Documents Department
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